Design and construction of special pressure-guide tube for measurement of ROSA-III core inlet flow rate

Shinichi Morooka, Osamu Kikuchi, Nobuhiko Inai, Hideo Murata, Kanji Tasaka

Research output: Contribution to journalArticle

Original languageEnglish
Pages (from-to)387-388
Number of pages2
JournalJournal of Nuclear Science and Technology
Volume18
Issue number5
DOIs
Publication statusPublished - 1981
Externally publishedYes

Keywords

  • BWR type reactors
  • Cooling water
  • Core inlet ttow rate
  • Fuel assemblies
  • Fuel cans
  • Heat transfer
  • High pressure
  • High temperature
  • Loss of coolant
  • Pressure-guide tube
  • Rig of safety assessment

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Nuclear and High Energy Physics

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